Mixed Elastic Scattering Format Proposal

Mixed Elastic Scattering Format Proposal
M. L. Zerkle
CSEWG – Formats & Processing Committee
November 30, 2020
Motivation
Selected nuclides exhibit both coherent
and incoherent elastic scattering effects in
the thermal energy range
More rigorous thermal elastic scattering
treatment needed to support advanced
moderator development
Without treatment Bragg peaks either
neglected (incoherent approximation) or to
deep (coherent approximation)
Mixed Elastic Scattering format is a simple
extension to ENDF-6 format
Provides support for new capability in GNDS
No impact
 on existing TSL evaluations
Implementation
7
LiD and 
7
LiH TSL evaluations
FLASSH TSL evaluation code (to be released)
NDEX nuclear data processing code
MC21 neutron transport code
2
Bound Scattering Cross Sections for Selected Nuclides (b) 
D(
7
LiD) Mixed Elastic Scattering TSL Evaluation
3
7
LiD coherent and D incoherent elastic scattering 
cross sections approximately the same magnitude
Both coherent and incoherent elastic scattering
effects captured in NDEX total elastic scattering
cross sections
7
Li(
7
LiD) Mixed Elastic Scattering TSL Evaluation
4
7
LiD coherent elastic scattering component larger
than 
7
Li incoherent elastic scattering
7
LiD Bragg scattering more prominent in 
7
Li(
7
LiD)
total scattering cross sections from NDEX
ENDF-6 Format Proposal
5
D(7LiD) Mixed Elastic Scattering Example
 1.150000+2 1.996800+0          3          0          0          0  15 7  2
 2.936000+2 0.000000+0          5          0          1       3374  15 7  2
       3374          1                                              15 7  2
 1.235573-3 2.67690-34 2.471146-3 5.24780-34 3.706719-3 3.757353-3  15 7  2
 4.942291-3 1.386287-2 6.177864-3 1.386287-2 7.413437-3 1.386287-2  15 7  2
 9.884583-3 2.595574-2 1.112016-2 2.595574-2 1.235573-2 2.595574-2  15 7  2
 1.359130-2 2.992438-2 1.482687-2 3.549502-2 1.606245-2 3.549502-2  15 7  2
 4.399400-2 4.399400-2 4.399400-2 4.399400-2 4.399400-2 4.399400-2  15 7  2
 4.399400-2 4.399400-2                                              15 7  2
 2.054202+0 0.000000+0          0          0          1          6  15 7  2
          6          2                                              15 7  2
 2.936000+2 8.937898+0 4.000000+2 1.047985+1 5.000000+2 1.213545+1  15 7  2
 6.000000+2 1.390890+1 7.000000+2 1.575652+1 8.000000+2 1.765328+1  15 7  2
 0.000000+0 0.000000+0          0          0          0          0  15 7  0
 1.150000+2 1.996800+0          0          1          0          0  15 7  4
 0.000000+0 0.000000+0          0          0          6          0  15 7  4
 3.395004+0 1.976285+2 1.996800+0 5.000000+0 0.000000+0 1.000000+0  15 7  4
 0.000000+0 0.000000+0          0          0          1        300  15 7  4
        300          4                                              15 7  4
 2.936000+2 0.000000+0          5          0          1        200  15 7  4
        200          4                                              15 7  4
 2.059042-2 4.931327-4 2.163677-2 5.181545-4 2.273629-2 5.444438-4  15 7  4
 2.389168-2 5.720646-4 2.510579-2 6.010840-4 2.638160-2 6.315727-4  15 7  4
6
LTHR=3
Coherent Elastic
Incoherent Elastic
Inelastic
Bound incoherent
scattering cross section
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This proposal focuses on introducing a Mixed Elastic Scattering format to address the need for a more rigorous treatment of thermal elastic scattering effects in selected nuclides. The format extension, compatible with ENDF-6, supports advanced moderator development without impacting existing TSL evaluations. Implementation involves FLASSH TSL evaluation code, NDEX nuclear data processing code, and MC21 neutron transport code. Examples illustrate the treatment of coherent and incoherent elastic scattering effects, with a particular emphasis on 7LiD and 7Li(7LiD) systems.

  • Elastic Scattering
  • Nuclear Data
  • Format Proposal
  • Advanced Moderator Development
  • Thermal Effects

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  1. Mixed Elastic Scattering Format Proposal M. L. Zerkle CSEWG Formats & Processing Committee November 30, 2020 The Naval Nuclear Laboratory is operated for the U.S. Department of Energy by Fluor Marine Propulsion, LLC, a wholly owned subsidiary of Fluor Corporation.

  2. Motivation Selected nuclides exhibit both coherent and incoherent elastic scattering effects in the thermal energy range More rigorous thermal elastic scattering treatment needed to support advanced moderator development Without treatment Bragg peaks either neglected (incoherent approximation) or to deep (coherent approximation) Mixed Elastic Scattering format is a simple extension to ENDF-6 format Provides support for new capability in GNDS No impact on existing TSL evaluations Implementation FLASSH TSL evaluation code (to be released) NDEX nuclear data processing code MC21 neutron transport code Bound Scattering Cross Sections for Selected Nuclides (b) ?? ?? ?? Nuclide natH 1.7568(10) 80.26(6) 82.02(6) 1H 1.7583(10) 80.27(6) 82.03(6) 2H 5.592(7) 2.05(3) 7.64(3) natLi 0.454(10) 0.92(3) 1.37(3) 6Li 0.51(5) 0.46(5) 0.97(7) 7Li 0.619(11) 0.78(3) 1.40(3) natB 0.354(5) 1.70(12) 5.24(11) 7LiD and 7LiH TSL evaluations 10B 0.144(8) 3.0(4) 3.1(4) 11B 5.56(7) 0.21(7) 5.77(10) 23Na 1.66(2) 1.62(3) 3.28(4) 2

  3. D(7LiD) Mixed Elastic Scattering TSL Evaluation Both coherent and incoherent elastic scattering effects captured in NDEX total elastic scattering cross sections 7LiD coherent and D incoherent elastic scattering cross sections approximately the same magnitude 3

  4. 7Li(7LiD) Mixed Elastic Scattering TSL Evaluation 7LiD coherent elastic scattering component larger than 7Li incoherent elastic scattering 7LiD Bragg scattering more prominent in 7Li(7LiD) total scattering cross sections from NDEX 4

  5. ENDF-6 Format Proposal 5

  6. D(7LiD) Mixed Elastic Scattering Example LTHR=3 1.150000+2 1.996800+0 3 0 0 0 15 7 2 2.936000+2 0.000000+0 5 0 1 3374 15 7 2 3374 1 15 7 2 1.235573-3 2.67690-34 2.471146-3 5.24780-34 3.706719-3 3.757353-3 15 7 2 4.942291-3 1.386287-2 6.177864-3 1.386287-2 7.413437-3 1.386287-2 15 7 2 9.884583-3 2.595574-2 1.112016-2 2.595574-2 1.235573-2 2.595574-2 15 7 2 1.359130-2 2.992438-2 1.482687-2 3.549502-2 1.606245-2 3.549502-2 15 7 2 4.399400-2 4.399400-2 4.399400-2 4.399400-2 4.399400-2 4.399400-2 15 7 2 4.399400-2 4.399400-2 15 7 2 2.054202+0 0.000000+0 0 0 1 6 15 7 2 6 2 15 7 2 2.936000+2 8.937898+0 4.000000+2 1.047985+1 5.000000+2 1.213545+1 15 7 2 6.000000+2 1.390890+1 7.000000+2 1.575652+1 8.000000+2 1.765328+1 15 7 2 0.000000+0 0.000000+0 0 0 0 0 15 7 0 1.150000+2 1.996800+0 0 1 0 0 15 7 4 0.000000+0 0.000000+0 0 0 6 0 15 7 4 3.395004+0 1.976285+2 1.996800+0 5.000000+0 0.000000+0 1.000000+0 15 7 4 0.000000+0 0.000000+0 0 0 1 300 15 7 4 300 4 15 7 4 2.936000+2 0.000000+0 5 0 1 200 15 7 4 200 4 15 7 4 2.059042-2 4.931327-4 2.163677-2 5.181545-4 2.273629-2 5.444438-4 15 7 4 2.389168-2 5.720646-4 2.510579-2 6.010840-4 2.638160-2 6.315727-4 15 7 4 Coherent Elastic Bound incoherent scattering cross section Incoherent Elastic Inelastic 6

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